NEUTRON DOSE RATE ANALYSIS OF THE NEW CONSTOR® STORAGE CASK FOR THE RBMK-1500 SPENT NUCLEAR FUEL

Ernestas Narkunas; Arturas   Smaizy; Povilas Poskas; Valerij Naumov; Dmitrij Ekaterinichev

doi:https://doi.org/10.1016/j.net.2020.11.022

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자료유형: 학술저널

저자정보: Ernestas Narkunas (Nuclear Engineering Laboratory, Lithuanian Energy Institute) Arturas Smaizy (Nuclear Engineering Laboratory, Lithuanian Energy Institute) Povilas Poskas (Nuclear Engineering Laboratory, Lithuanian Energy Institute) Valerij Naumov (SE Ignalina Nuclear Power Plant) Dmitrij Ekaterinichev (SE Ignalina Nuclear Power Plant)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제6호

발행연도: 2021.6

수록면: 1,869 - 1,877 (9page)

DOI: https://doi.org/10.1016/j.net.2020.11.022

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This paper presents the neutron dose rate analysis of the new CONSTOR® RBMK-1500/M2 storage caskintended for the spent nuclear fuel storage at Ignalina Nuclear Power Plant in Lithuania. These casks aredesigned to be stored in a new “closed” type interim storage facility, with the capacity to store up to 202CONSTOR® RBMK-1500/M2 casks. In 2016 y, the “hot trials” of this new facility were conducted and 10CONSTOR® RBMK-1500/M2 casks loaded with the spent nuclear fuel were transported to the dedicatedstorage places in this facility. During “hot trials”, the dose rate measurements of the CONSTOR® RBMK-1500/M2 casks were performed as the dose rate is one of the critical parameter to control and it must bebelow design (and safety) criteria. Therefore, having the actual data of the spent nuclear fuel characteristics,the neutron dose rate modeling of the CONSTOR® RBMK-1500/M2 cask loaded with thisparticular fuel was also performed. Neutron dose rate modeling was performed using MCNP 5 computercode with very detailed geometrical representation of the cask and the fuel. The obtained modelingresults were compared with the measurement results and it was revealed, that modeling results aregenerally in good agreement with the measurements

#Neutron dose rate #CONSTOR® RBMK-1500/M2 storage cask #RBMK-1500 spent nuclear fuel

참고문헌 (15)

참고문헌 신청

GNS / 2007 / Lithuanian Energy Institute, Interim Storage of RBMK Spent Nuclear Fuel from Ignalina NPP Units 1 and 2

RadEye™ NL personal highly sensitive neutron radiation detectors

Oak Ridge National Laboratory / 2011 / SCALE: a Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design Version 6.1.

X-5 Monte Carlo Team / 2003 / MCNP e a General Monte Carlo N-Particle Transport Code, vols. I-III, (LA-UR-03-1987, LA-CP-03-0245, LA-CP-03-0284), Version 5

A. Smaizys / 2014 / Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuel / Nucl. Eng. Des 277:28~35

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